EP0219038B1 - Nuclear fuel assembly - Google Patents

Nuclear fuel assembly Download PDF

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Publication number
EP0219038B1
EP0219038B1 EP86113853A EP86113853A EP0219038B1 EP 0219038 B1 EP0219038 B1 EP 0219038B1 EP 86113853 A EP86113853 A EP 86113853A EP 86113853 A EP86113853 A EP 86113853A EP 0219038 B1 EP0219038 B1 EP 0219038B1
Authority
EP
European Patent Office
Prior art keywords
fuel
rod
sub
rods
bundle
Prior art date
Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
Expired - Lifetime
Application number
EP86113853A
Other languages
German (de)
English (en)
French (fr)
Other versions
EP0219038A2 (en
EP0219038A3 (en
Inventor
Jan Blomstrand
Sigvard Junkrans
Olov Nylund
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
Westinghouse Electric Sweden AB
Original Assignee
ASEA Atom AB
Priority date (The priority date is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the date listed.)
Filing date
Publication date
Application filed by ASEA Atom AB filed Critical ASEA Atom AB
Publication of EP0219038A2 publication Critical patent/EP0219038A2/en
Publication of EP0219038A3 publication Critical patent/EP0219038A3/en
Application granted granted Critical
Publication of EP0219038B1 publication Critical patent/EP0219038B1/en
Anticipated expiration legal-status Critical
Expired - Lifetime legal-status Critical Current

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Classifications

    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
    • G21C3/30—Assemblies of a number of fuel elements in the form of a rigid unit
    • G21C3/32—Bundles of parallel pin-, rod-, or tube-shaped fuel elements
    • G21C3/326—Bundles of parallel pin-, rod-, or tube-shaped fuel elements comprising fuel elements of different composition; comprising, in addition to the fuel elements, other pin-, rod-, or tube-shaped elements, e.g. control rods, grid support rods, fertile rods, poison rods or dummy rods
    • G21C3/328—Relative disposition of the elements in the bundle lattice
    • Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00—Energy generation of nuclear origin
    • Y02E30/30—Nuclear fission reactors
    • Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y10—TECHNICAL SUBJECTS COVERED BY FORMER USPC
    • Y10S—TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y10S376/00—Induced nuclear reactions: processes, systems, and elements
    • Y10S376/90—Particular material or material shapes for fission reactors

Definitions

  • the invention relates to a nuclear fuel assembly according to the precharacterising part of claim 1.
  • Fuel assemblies of this kind are known, for example, form EP-B-0 036 142 and EP-B-0 050 837.
  • these known fuel assemblies comprise sixty four fuel rods per assembly with the rods being divided into four groups, so-called sub-bundles, each one containing 4x4 fuel rods.
  • the cladding tubes of the fuel rods have a maximum external diameter of 12,25 mm and a minimum external diameter of 11,63 mm and a wall thickness within the interval of 0,74 - 0,80 mm.
  • the fuel pellets in the fuel rods have a diameter within the interval of 9,94 - 10,44 mm and their diameters are about 0,20 mm smaller than the interval diameter of the cladding tube.
  • the distance between the envelope surfaces of two adjacent fuel rods, arranged in the same row is between 3,55 and 3,87 mm in each sub-bundle.
  • the width of that part of the channel for water which is located between two adjacently positioned sub-bundles is, in the supplied fuel assemblies, at most 5,8 mm and at least 4 mm.
  • a fuel assembly having a larger number of fuel rods than 4x4 in each sub-bundle while maintaining the external dimensions of the fuel assembly in order to reduce the linear load on the fuel rod, that is, the power per unit of length of the rod, and hence the risk of the cladding tube being damaged by stresses caused by fuel pellets during operation of the reactor.
  • the EP-A-0 099 322 recommends the use of about 80 fuel rods in the fuel assembly and describes various geometric patterns for positioning the fuel rods in the duel assembly and its sub-bundles. Among them there are fuel assemblies which included a sub-bundle containing 5x5 fuel rods.
  • the invention aims at a nuclear fuel assembly of the above-mentioned kind allowing the accommodation of 100 fuel rods in a fuel channel without encountering the difficulties described above.
  • the invention suggests a nuclear fuel assembly according to the introductory part of claim 1, which is characterized by the features of the characterizing part of claim 1.
  • the fuel pellets in the fuel rods preferably have a diameter of 7,4 - 8,8 mm. This diameter is preferably 0,14 - 0,20 mm smaller than the internal diameter of the cladding tubes.
  • the distance between the envelope surfaces of two fuel rods located in the same row of fuel rods in a sub-bundle preferably amounts to 2,4 - 3,9 mm and the distance between a fuel rod, located adjacent to a side wall in the fuel channel, and said wall as well as the distance between a fuel rod, located adjacent to a wall in the channel for water, and said wall in the channel preferably amount to 2,0 -4,0 mm.
  • the width of that part of the channel for water which is located between two adjoining sub-bundles is preferably 3,0 - 8,0 mm. In certain cases a width of 6,0 - 8,0 mm is preferable.
  • the distance between the spacers in a sub-bundle may advantageously amount to 400-600 mm.
  • a low internal form factor is attained because of the existence of the water channel with a cruciform cross-section. It permits the use of a greater axial form factor, which can be utilized for fuel saving by arranging pellets of oxide of natural uranium at the ends of the fuel rods.
  • the centre rod in each sub-bundle containing 5x5 rods is used as a tie rod for the sub-bundle.
  • the centre rod can then be used for carrying fuel.
  • it can also he used as a tie rod in the form of a water-filled rod.
  • a desired symmetrical mechanical load can be achieved while utilizing one single rod in the sub-bundle.
  • This centre rod whether it is fuel-carrying or water-filled, can also be advantageously used as a spacer holder rod.
  • 1 designates a fuel channel of substantially square cross-section.
  • the fuel channel 1 surrounds, with no significant play, an upper, square portion of a bottom part 2 having a circular, downwardly facing inlet opening 3 for cooling water and moderator water.
  • the bottom part 2 supports a supporting plate 4.
  • the fuel channel 1 has a relatively thick wall portion which is fixed to the bottom part 2 and the supporting plate 4 by means of a plurality of horizontal bolts, indicated by means of dash-dotted lines 5.
  • the fuel channel 1 is divided into four vertical sub-channels 6 by means of a hollow channel-forming member 7 of cruciform cross-section which forms the above-mentioned vertical channel for water, and which is welded to the four walls 1a,1b,1c and 1d of the fuel channel 1.
  • the channel-forming member 7 has four hollow wings 8. At the bottom the channel-forming member 7 is connected to an inlet tube 9 for moderator water.
  • the sub-channels 6 each contain one sub-bundle 25 containing twenty-five fuel rods 10.
  • the rods are arranged in a symmetrical lattice in five rows, each containing five rods. Each rod is included in two rows perpendicular to each other.
  • Each sub-bundle is arranged with a grid-like bottom tie plate 11, a grid-like top tie plate 12 and a plurality of spacers 13.
  • the fuel channel 1, the channel-forming member 7 and the spacer 13 are all of a zirconium alloy, such as Zircaloy 4.
  • the four bottom tie plates 11 are supported by the supporting plate 4 and are each partially inserted into a respective square hole 14 therein.
  • each sub-bundle at least one of the fuel rods is made with relatively long, threaded end plugs, the lower end plug being passed through the bottom tie plate 11 and being provided with a nut 15, the upper end plug being passed through the top tie plate 12 and being provided with a nut 16.
  • the centre rod 26 which is formed in this way. This rod serves as a spacer holder rod.
  • An upper end portion of the fuel channel 1 surrounds a cruciform lifting plate 17 having four horizontal arms 18,19,20 and 21, which extend from a common central portion. At its outer end each arm has a portion 22 in the form of an arrow-head. In each corner of the fuel channel 1 each of these portions 22 makes contact with the inner wall surface of the fuel channel 1.
  • a lifting handle 23 is fixed at the arms 20 and 21. The lifting plate 17 and the lifting handle 23 together may form a solid-cast lifting member of steel.
  • the lifting plate 17 is fixed to the channel-forming member 7 by inserting each of four vertical bars 28 into a respective wing 8 of the channel-forming member 7 and welding them thereto.
  • each bar 28 has a vertical, bolt-like portion 29 which is passed, with a play, through a corresponding hole in the central portion of the lifting plate 17 and is provided with a nut 30.
  • the fuel channel 1 is provided with indentations 31, intermittently arranged in the longitudinal direction, against which the wings of the channel-forming member 7 are welded.
  • the cladding tube of the fuel rods has a wall thickness of 0,50 - 0,70 mm and an outer diameter of 8,5 - 10,3 mm.
  • the distance a ( Figure 3) between two fuel rods located adjacent to each other in the same row is, in the exemplified case, 3,0 mm. This applies to both of the rows which are perpendicular to each other and in which each fuel rod is included.
  • the distance b between a fuel rod, located adjacent to a wall in the fuel channel 1, and said wall amounts to 2,8 mm.
  • the width d of that part 8 of the channel-forming member which is located between two adjacent sub-bundles 25 is, in the exemplified case, 6 mm.
  • each fuel rod 10 includes a cladding tube 41, made of a zirconium alloy, such as Zircaloy 2.
  • the cladding tube 41 has a length of about four meters and contains about 300 circular-cylindrical pellets 42 stacked one above the other in the axial direction of the tube.
  • the pellets have a height of 11 mm and a diameter of 8,0 mm.
  • the pellets located nearest to each end of the fuel rods which pellets consist of oxide of natural uranium
  • the pellets consist, in a conventional manner, of uranium dioxide, which is enriched with respect to U 235.
  • the bottom pellet rests rigidly on an end plug 43 welded to the lower end of the rod, and the top pellet is pressed downwards by a helical spring 44 which is tightened against an end plug 45 welded to the upper end of the tube.
  • the pellets are ground to such dimensions as to form a play 46 between the envelope surface of the pellet and the inner wall of the cladding tube.
  • the thickness of the cladding tube amounts to 0,60 mm and its outer diameter to 9,4 mm.
  • the fuel rod is filled with helium with a pressure of 4 MPa.
  • center rod 26 instead of being formed as a fuel-carrying rod used as a spacer holder rod, may be formed as a water-filled tie rod and/or a spacer holder rod. Also certain of the remaining rods in each sub-bundle may be formed as water-filled rods instead of as fuel rods.

Landscapes

  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)
  • Catalysts (AREA)
  • Solid Fuels And Fuel-Associated Substances (AREA)
EP86113853A 1985-10-16 1986-10-07 Nuclear fuel assembly Expired - Lifetime EP0219038B1 (en)

Applications Claiming Priority (2)

Application Number Priority Date Filing Date Title
SE8504811 1985-10-16
SE8504811A SE450177B (sv) 1985-10-16 1985-10-16 Kernbrenslepatron

Publications (3)

Publication Number Publication Date
EP0219038A2 EP0219038A2 (en) 1987-04-22
EP0219038A3 EP0219038A3 (en) 1987-11-25
EP0219038B1 true EP0219038B1 (en) 1991-07-31

Family

ID=20361771

Family Applications (1)

Application Number Title Priority Date Filing Date
EP86113853A Expired - Lifetime EP0219038B1 (en) 1985-10-16 1986-10-07 Nuclear fuel assembly

Country Status (7)

Country Link
US (1) US4749547A (fi)
EP (1) EP0219038B1 (fi)
JP (1) JP2502543B2 (fi)
DE (1) DE3680629D1 (fi)
ES (1) ES2004862A6 (fi)
FI (1) FI83823C (fi)
SE (1) SE450177B (fi)

Families Citing this family (20)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4803044A (en) * 1986-04-10 1989-02-07 Advanced Nuclear Fuels Corporation Bwr assembly
US4818478A (en) * 1987-12-07 1989-04-04 Westinghouse Electric Corp. BWR fuel assembly mini-bundle having interior fuel rods of reduced diameter
JP2713983B2 (ja) * 1988-05-19 1998-02-16 株式会社東芝 原子炉用燃料集合体
DE8815433U1 (de) * 1988-12-12 1989-02-23 Siemens AG, 1000 Berlin und 8000 München Brennstab für ein Brennelement eines Druckwasser-Kernreaktors
US4957698A (en) * 1989-02-17 1990-09-18 Advanced Nuclear Fuels Corporation Advanced boiling water reactor fuel assembly design
SE465191B (sv) * 1989-12-14 1991-08-05 Asea Atom Ab Braenslepatron foer en kaernreaktor av kokarvattentyp
SE465192B (sv) * 1989-12-15 1991-08-05 Asea Atom Ab Braenslepatron foer en kaernreaktor av laettvattentyp
US5488644A (en) 1994-07-13 1996-01-30 General Electric Company Spring assemblies for adjoining nuclear fuel rod containing ferrules and a spacer formed of the spring assemblies and ferrules
US5519747A (en) 1994-10-04 1996-05-21 General Electric Company Apparatus and methods for fabricating spacers for a nuclear fuel rod bundle
US5519746A (en) * 1994-11-28 1996-05-21 General Electric Company Large BWR fuel channel design
US5546437A (en) 1995-01-11 1996-08-13 General Electric Company Spacer for nuclear fuel rods
US5566217A (en) 1995-01-30 1996-10-15 General Electric Company Reduced height spacer for nuclear fuel rods
US5675621A (en) 1995-08-17 1997-10-07 General Electric Company Reduced height flat spring spacer for nuclear fuel rods
US5646973A (en) * 1995-10-12 1997-07-08 General Electric Company BWR fuel assembly without upper tie plate
US5610961A (en) * 1995-10-12 1997-03-11 General Electric Company Fuel assembly structure using channel for load support
SE517867C2 (sv) 1995-10-12 2002-07-23 Gen Electric Vattenstav i ett bränsleaggregat tillhörigt en kokvattenreaktor
US5627866A (en) * 1995-10-12 1997-05-06 General Electric Company Fuel assembly structure using channel for load support
US5748695A (en) * 1995-11-07 1998-05-05 General Electric Company Fuel assembly structure selectively using channel and coolant rod for load support and method
FR2817385B1 (fr) * 2000-11-30 2005-10-07 Framatome Anp Pastille de combustible nucleaire oxyde et crayon comportant un empilement de telles pastilles
WO2011143172A1 (en) * 2010-05-11 2011-11-17 Thorium Power, Inc. Fuel assembly with metal fuel alloy kernel and method of manufacturing thereof

Family Cites Families (7)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
SE421969B (sv) * 1980-03-17 1982-02-08 Asea Atom Ab Brenslepatron for en kokarreaktor
JPS5736017A (en) * 1980-08-15 1982-02-26 Hitachi Ltd Manufacture of sheath for nuclear fuel element
SE426530B (sv) * 1981-05-15 1983-01-24 Asea Atom Ab Brenslepatron avsedd for en kokvattenreaktor
JPS58135989A (ja) * 1982-02-08 1983-08-12 株式会社日立製作所 沸騰水型原子炉燃料集合体
SE433986B (sv) * 1982-07-12 1984-06-25 Asea Atom Ab Kernbrenslepatron
US4567017A (en) * 1983-12-16 1986-01-28 The United States Of America As Represented By The United States Department Of Energy Fuel pin cladding
US4613479A (en) * 1984-03-14 1986-09-23 Westinghouse Electric Corp. Water reactor fuel cladding

Also Published As

Publication number Publication date
DE3680629D1 (de) 1991-09-05
FI83823C (fi) 1991-08-26
FI864153A (fi) 1987-04-17
FI83823B (fi) 1991-05-15
US4749547A (en) 1988-06-07
ES2004862A6 (es) 1989-02-16
EP0219038A2 (en) 1987-04-22
FI864153A0 (fi) 1986-10-14
SE8504811L (sv) 1987-04-17
SE8504811D0 (sv) 1985-10-16
JPS6293689A (ja) 1987-04-30
EP0219038A3 (en) 1987-11-25
SE450177B (sv) 1987-06-09
JP2502543B2 (ja) 1996-05-29

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